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Meeting MS&T23: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments IV
Presentation Title Accelerated Creep Testing for High-Temperature and Nuclear Applications
Author(s) Calvin M. Stewart, Jacob Pellicotte, Md Abir Hossain
On-Site Speaker (Planned) Calvin M. Stewart
Abstract Scope In this study, accelerated creep tests are presented that accelerate the capture-of-creep resistance data for materials. Creep is a time-dependent phenomenon that grows over decades in high temperature components and can contribute to failure. Code qualified materials (under ASME BPVCIII) must have 10,000 hours of creep testing data for each HEAT (up to 30,000 hours depending on metastability). Consequently, creep tests are time intensive, requiring numerous tests that span design stresses, temperatures, and materials of interest. To enable the materials genome initiative for nuclear structural materials, the timeline for capturing creep resistance data must be shortened. In this study, the stepped isostress method (SSM) and dynamic negative stepped tests (DNST) are presented and demonstrated on a wrought and additive manufactured materials respectively. Future concepts for in-pile accelerate creep testing to investigate irradiation induced creep are discussed.


Accelerated Assessment of Microstructure-Mechanical Property Relationships in Ni Based Superalloys
Accelerated Creep Testing for High-Temperature and Nuclear Applications
Advanced In-situ Strain Mapping for Zr Oxidation by 4D-STEM
Assessing the Ability of Nuclear Fuel Performance Codes to Predict Radially Resolved Properties in Oxide Fuels
Capturing 3D Evolution of Twin Networks in Titanium as a Function of Applied Strain
Effect of Solutes on the Radiation Induced Segregation in Ferritic Alloys at ∑3- grain Boundaries
Effect of Strain Rate on Tensile Properties of C250 Maraging Steel
Enabling Multiscale Materials Characterization with Machine Learning
Four-dimensional Scanning Transmission Electron Microscopy (4D-STEM) Characterization of Intergranular Corrosion of Austenitic Stainless Steels in Lead-bismuth Eutectic
High-Temperature Irradiation Behavior of Piezoelectric Aluminum Nitride
In Situ SEM Nanomechanics at Cryogenic Temperatures
Interdiffusion Behaviour of UN with Zircaloy-4 via Diffusion Couple Studies
M-1: Novel Method for Fabricating and Analysis of 3D Printed Composite for Radiation Shielding Containing Metalized Halloysite Nanotube
Mapping Elemental Distributions Across Thin Corrosion Films Formed on Nuclear Reactor Core and Structural Materials via Ex-situ And In-situ Atom Probe Tomography
Multimodal Characterization of Materials Corrosion in Molten Salts
Phase Stability of Delta-ZrH Under Ion Irradiation
Probing Nanoscale Properties of Radioactive Material by Advanced Correlative Microscopy
STEM-based Mapping of Nanoscale Point Defects Produced via Temperature, Irradiation, And Corrosion
Structural Stability of REE-PO4 (REE=Sm,Tb) under Swift Heavy Ion Irradiation
Thermodynamic Modeling and Calculation of Phase Formation Processes Under Irradiation Conditions of Uranium-plutonium Nitride Fuel
Transition Metal Carbonitride Materials Exposed to Swift Heavy Ions

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